Tungsten coating on JET divertor tiles for erosion/deposition studies

Sari Lehto (Corresponding Author), Jari Likonen, J.P. Coad, T. Ahlgren, D.E. Hole, M. Mayer, H. Maier, J. Kolehmainen

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    32 Citations (Scopus)

    Abstract

    Six Joint European Torus (JET) divertor tiles were coated with tungsten marker stripes for erosion/deposition studies. The average thickness was 3.4 μm and the film was uniform within 5% across and within 10% along the stripe. Small amounts of impurities C, Fe, Ni and Cr were found and the in-plane stress was 965 MPa. Resistance to high heat loads was tested in the Neutral Beam Test-bed at JET where a coated carbon fibre composite block was exposed to a total of 113 pulses with a maximum peak power density of 15.7 MW m−2 and a maximum surface temperature of 1280 °C. No visible changes as a result of thermal cycling nor sputtering of the film by deuterium could be detected.
    Original languageEnglish
    Pages (from-to)241-245
    Number of pages5
    JournalFusion Engineering and Design
    Volume66-68
    DOIs
    Publication statusPublished - 2003
    MoE publication typeA1 Journal article-refereed
    Event22nd Symposium on Fusion Technology - Helsinki, Finland
    Duration: 9 Sep 200213 Sep 2002
    Conference number: 22

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    Keywords

    • tungsten coating
    • plasma
    • tungsten
    • erosion
    • deposition
    • divertor tiles
    • divertor
    • JET
    • ITER
    • fusion energy
    • fusion reactors

    Cite this

    Lehto, S., Likonen, J., Coad, J. P., Ahlgren, T., Hole, D. E., Mayer, M., Maier, H., & Kolehmainen, J. (2003). Tungsten coating on JET divertor tiles for erosion/deposition studies. Fusion Engineering and Design, 66-68, 241-245. https://doi.org/10.1016/S0920-3796(03)00291-6